ML20034H216

Amends 143 & 132 to Licenses DPR-39 & DPR-48,respectively, Revising TS by Incorporating Alternative Methods for Controlling High Radiation Areas

ML20034H216
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	03/11/1993
From:	Dyer J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20034H215	List: ML20034H214 ML20034H216 ML20034H218
References
NUDOCS 9303160188
Download: ML20034H216 (9)

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UNITED STATES 2,

NUCLEAR REGULATORY COMMISSION c.

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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 143 License No. DPR-39 1

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated April 1, 1991, as supplemented on October 26, 1992, complies with the standards and requirements of the-Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the-health and safety of the public; and E.

The issuance of this amendment-is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-39 is hereby amended to read as follows:

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9303160188 930311 i

PDR ADOCK 05000295 p

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(2)

Technical Specificaticas The Technical Specifications contained in Appendices A and B, as revised through Amendment No.143, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION VRMk James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 11, 1993 h

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. UNITED STATES.

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q DOCKET NO. 50-304 ZION NUCLEAR POWER STATION.-UNIT 2'

.j AMENDMENT TO FACILITY OPERATING LICENSE w

' Amendment'No.-132:

License No. DPR-48 1.

The Nuclear Regulatory Commission (the Commission) has found'that:

-i A.

The application for amendment by Commonwealth-Edison Compa'ny (the 1icensee) dated April 1,1991, as supplemented on October 26,:

ll 1992, complies ~with the standards and-requirements of the Atomic'

. Energy Act of 1954, as amended (the Act)' and-the Comriiission's rules and regulations set forth in 10 CFR. Chapter.1; i

B.

The facility will operate-in conformity with the application the:

provisions of the' Act, and the rules and regulations.of the.

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Commission-i a

C.

- There is reasonable assurance (i) that the activities authorized..

by this amendment can be conducted without_ endangering the health:

ll and safety of the public, and (ii) that such activities'wil.1 be 1

conducted in compliance with.the Commission's regulations;..

3

-v D,

The issuance of this amendment will not'belinimical to the common j

defense and security or to the health and safety ofgthe public;

l and E.

The issuance of this amendment is in accordance with-10 CFRL

- 1 Part 51 of the Commission's regulations and all-applicable:

~j requirements have been satisfied.

q 2.

Accordingly, the license ~is. amended byL. changes ~to the.: Technical j

Specifications'as-indicated in'the attachment to thisilicense amendment-j and. paragraph 2.C.(2) of facility;0perating License No.-DPR-48-is hereby' i

amended.to' read as.follows:

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. l (2)

Technical Specifications i

The-Technical Specifications contained-in Appendices A and B,-:as revised.through Amendment No.132, are breeby incorporated ~in the~

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license. The licensee shall operate the f acility in accordance-1 with the Technical. Specifications.

3.

This license amendment is effective as of-the date of its issuance and-j shall be. implemented within 60 days of its; date of11ssuance..

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FOR THE NUCLEAR REGULATORY COMMISSION s _( V iM Q

--n James E. Dyer, Director.

Project. Directorate-III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation.

Attachment:

Changes to the Technical Specifications Date of Issuance:. March 11, 1993 f

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l ATTACHMENT T0 LICENSE AMENDMENTS i

AMENDMENT NO.143 TO FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO.132 TO FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are i

identified by the captioned amendment number and contain marginal lines indicating the area of change.

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Remove Paaes Jnsert Paaes 309 309 309a 309b 309c I

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I 6.2 Procedures and Programs 1.

Hrltten procedures including applicable checkoff lists covering items IIsted below shall be prepared, implemented, and maintained:

a.

The appilcable procedures recommended in Appendix A, of Regulatory Guide 1.33, Revision 2, February 1978;.

b.

The emergency operating procedures required to implement the requirements of NUREG-0737 and Supplement I to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33; c.

Station Security Plan implementation; d.

Generating Station Emergency Response Plan implementation; e.

PROCESS CONTROL PROGRAM 1mplementation; f.

OFFSITE DOSE CALCULATION MANUAL implementation; g.

Fire Protection Program implementation; h.

Post Accident Sampilng Program which will ensure the capability to: obtain and analyze reactor coolant and contalnnent atmosphere samples, and collect and analyze or measure radioactive lodine and particulates in plant gaseous effluents under accident conditions.

The program shall include the following:

(1) Training of personnel, (11) Procedures for sampling and analysts, (Ill) Provisions for maintenance of sampilng and analysis equipment.

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Working hours of the Shift Engineer, Shif t Control Room Engineer, Shif t foreman, and Nuclear Station Operator such that the heavy use of overtime is not routinely required.

309 Amendment Nos.

143 and 132

6.2.2 Radiation Protection _Prosr_am 6.2.2.A Radiation control procedures shall be prepared, implemented, and maintained.

These procedures shall specify.

permissible radiation exposure limits and shall be consistent with the requirements of 10 CFR 20. The radiation protection program shall meet the requirements of 10 CFR 20.

6.2.2.B High Radiation Area 6.2.2.B.1 Pursuant to Paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the " control device" or " alarm signal" required by paragraph 20.203(c), each high radiation area, as defined in 10 CFR Part 20, in which the Intensity of radiation is equal to or less than 1000 mrem /hr at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RHP).

Individuals quallfled in radiation protection procedures or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties In'hlgh radiation areas with exposure rates equal to or less than 1000 mrem /hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of Individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area; or b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset Integrated dose is received.

Entry into such areas with this monitoring device may be made after the_ dose rate levels in the area have been establ.lshed and personnel have been made knowledgeable of them; or c.

An individual quallfled in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the Radiation dork Permit.

309a Amendment Nos. 143 and 132 1

6.2.2.8 (Continued) 6.2.2.B.2

a. In addition to the requirements of Specification 6.2.2.B.1, areas accessible to personnel with radiation levels greater than 1000 mrem /hr at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates shall require the following:

1.

Locked doors to prevent unauthorized entry.

The keys shall be maintained under the administrative control of the operating shift supervision on duty and/or health physics supervision.

2.

Personnel access and exposure control over activities being performed within these areas shall be r

specified by an approved RHP.

During emergency situations which involve personnel injury or actions y

taken to prevent major equipment damage, continuous surveillance and radiation monitoring of the work area by an Individual'quallfled in radiation protection procedures may be substituted for the routine RHP procedure.

3.

Each person entering the area shall be provided with an alarming radiation monitoring device which k

f continuously integrates the radiation dose rate (such as an electronic dostmeter). Continuous coverage by a radiation technician may be substituted for alarming dostmetry,

b. For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mrem /hr at 30cm (12 in.), that are located within large areas (with the exception of 6.2.2.B.2.c),

including the containment outside the missile barrier, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the Individual area, that Individual area shall be barricaded (by a more substantial obstacle than a rope), conspicuously posted, and a flashing 11ght shall be activated as a warning device.

l 309b Amendment Mos.143 and 132

.o 26.2.2.B (Continued)

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c.'For. Individual high radiation areas accessible to personnel with radiation levels of greater than 1000

-mrem /hr-at 30 cm (12 In.), that are located within the containment-Inside the misslie barrier, where-no -

enclosure exists for purposes.of locking the individual area, the access control shall be per the following:'.

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1.

The miss11e' barrier Ingress / egress. points shall be barricaded, locked and conspicuously posted to prevent access; or

'2.

a..

The_ missile barrier' ingress / egress points shall be conspicuously posted and'have direct or-electronic' surveillance that is capable of. preventing. unauthorized entry;'.and

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b.

l Additional localized postings shall be provided in areas with normal personnel access inside the alsstle barrier to inform personnel of dose rates greater than 1000 mrea/hr at-30 cm-(12.

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a 309c

' Amendment Mos.. 143'and 132

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